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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Empowering the next generation: ANS’s newest book focuses on careers in nuclear energy
A new career guide for the nuclear energy industry is now available: The Nuclear Empowered Workforce by Earnestine Johnson. Drawing on more than 30 years of experience across 16 nuclear facilities, Johnson offers a practical, insightful look into some of the many career paths available in commercial nuclear power. To mark the release, Johnson sat down with Nuclear News for a wide-ranging conversation about her career, her motivation for writing the book, and her advice for the next generation of nuclear professionals.
When Johnson began her career at engineering services company Stone & Webster, she entered a field still reeling from the effects of the Three Mile Island incident in 1979, nearly 15 years earlier. Her hiring cohort was the first group of new engineering graduates the company had brought on since TMI, a reflection of the industry-wide pause in nuclear construction. Her first long-term assignment—at the Millstone site in Waterford, Conn., helping resolve design issues stemming from TMI—marked the beginning of a long and varied career that spanned positions across the country.
Volkan Seker, Haining Zhou, Thomas J. Downar
Nuclear Technology | Volume 206 | Number 6 | June 2020 | Pages 805-824
Technical Paper | doi.org/10.1080/00295450.2019.1703464
Articles are hosted by Taylor and Francis Online.
The Transient Reactor Test Facility (TREAT) was designed in the late 1950s to test nuclear fuels and materials under extreme conditions and has been recently restarted by the U.S. Department of Energy to provide the transient test capability to evaluate the performance of innovative nuclear fuels under accident conditions. Benchmark experiment data are required to support the operation of TREAT and to validate the computational analyses necessary to design and evaluate the experiments. Therefore, in this paper, benchmark problems based on the minimum critical (MC) core and M8 Power Calibration Experiment (M8CAL) core of TREAT were developed and analyzed using the Monte Carlo code Serpent. The eigenvalue, temperature coefficient, and flux distributions for both the MC core and the M8CAL cores were calculated and compared to the experimental data. All the calculated values compared well to the experimental data, and both problems were subsequently approved as International Reactor Physics Experiment Evaluation Project benchmarks.
